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Results from a One-Year Leach Test: Long-Term Use of Mcc-L*

Published online by Cambridge University Press:  15 February 2011

D. M. Strachan
D. M. Strachan*
Affiliation:
Pacific Northwest Laboratory, P. O. Box 999, Richland, Washington, 99352, USA
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Extract

The Nuclear Waste Materials Characterization Center at Pacific Northwest Laboratory is developing standard tests to obtain data on nuclear waste forms, barriers, and backfills. These tests include performance measurements of thermal, radiation, mechanical, and chemical properties. Five tests have been developed to determine the chemical durability of waste forms under either static (MCC-IP and MCC-2P) or flowing (MCC-4S and MCC-5S) leaching environments. Maximum credible release by waste forms is determined using powders and stirred solutions (MCC-3S).

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 11: Symposium – Scientific Basis for Nuclear Waste Management V , 1981 , 181
Copyright
Copyright © Materials Research Society 1982

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Footnotes

*

This work was supported by the U.S. Department of Energy under contract DE-AC06-76RLO 1830.

References

REFERENCES

1. Materials Characterization Center (1981) Nuclear Waste Materials Handbook DOE/TIC-11400, Pacific Northwest Laboratory, Richland, WA, USA Google Scholar
2. Materials Characterization Center (1981) Materials Characterization Center Test Methods - Preliminary Version, PNL-3990, Pacific Northwest Laboratory, Richland, WA, USA. Google Scholar
3. Strachan, D.M. and Barnes, B.O. (1981) The Leachability of Some Nuclear Waste Forms, PNL-SA-9118, Pacific Northwest Laboratory, Richland, WA, USA Google Scholar
4. Jantzen, C.M. Clarke, D.R. Morgan, P.E.D. and Harker, A.B. (1982) The Leaching of Tailored Polyphase Nuclear Waste Ceramics: Microstructural and Phase Characterization. J. Amer. Cer. Soc., Vol. 65 pp. 292–300 10.1111/j.1151-2916.1982.tb10447.xCrossRefGoogle Scholar
5. Campbell, J.H. Hoenig, C.L. Bazan, F. Ryerson, F.J. and Rozsa, R.B. (1981). Immobilization of Savannah River High-Level Wastes in SYNROC: Results from Performance Tests. UCRL-86753, Lawrence Livermore Laboratory, Livermore, CA, USA. Google Scholar
6. Stone, J.A. (1981) An Experimental Comparison of Alternative Solid Forms for Savannah River High-Level Wastes. DP-MS-81-102, Savannah River Laboratory, Aiken, SC, USA.Google Scholar
7. ACS (1980) Guidelines for Data Acquisition and Data Quality Evaluation in Environmental Chemistry. ACS Committee on Environmental Improvement. Analytical Chem. 52, 2242–2249.Google Scholar
8. Marshall, W.L. (1980) Amorphous Silica Solubilities-I. Behavior in Aqueous Sodium Nitrate Solutions; 25–300°C, 0–6 Molal. Geochemica et Cosmochemica Acta, 44, 907–913.10.1016/0016-7037(80)90280-XGoogle Scholar
9. Iler, R.K. (1979) The Chemistry of Silica: Solubility, Polymerization, Colloid, and Surface Properties, and Biochemistry. John Wiley and Sons, New York, NY, USA.Google Scholar
10. Fullam, H.T. (1981) Solubility Effects in Waste-Glass/Demineralized Water Systems. PNL-3614. Pacific Northwest Laboratory, Richland, WA, USA.Google Scholar
11. Grambow, B.E.E. (1982) The Role of Metal Ion Solubility in the Leaching of Nuclear Waste Glasses. PNL-SA-10079. Pacific Northwest Laboratory, Richland, WA, USA (also this publication).Google Scholar
12. Kester, D.R. O'Conner, T.P., and Byrne, R.H. Jr. (1975) Solution Chemistry, Solubility, and Adsorption Equilibria of Iron, Cobalt, and Copper in Marine Systems. Thalassia Jugoslavia, 11(2), 121–134.Google Scholar